Hydrogen Isotope Research Center - Toyama Univ.

Data Base for Tritium Solid Breeding Materials (Li₂O, Li₂TiO₃, Li₂ZrO₃ and Li₄SiO₄) of Fusion Reactor Blankets --- Yoshiaki FUTAMURA

8. Concluding Remarks

  Authors have compiled the up-to-date data for candidate blanket solid breeding materials, which have been collected by this time, and assessed these data. There are less data for Li₂TiO₃ than those for Li₂O, Li₂ZrO₃ and Li₄SiO₄, although Li₂TiO₃ is recently considered as an attractive candidate breeding material.
  As a whole, physical properties and thermal properties are fairly good investigated, but the investigations are not enough. More investigations for fracture strength, specially, tensile and bending strength of breeder ceramics, are required. Data for thermal creep of Li₂ZrO₃ and for thermal cycling strength of breeder ceramics are required.
  With regard to compatibility, the data on hydrogen solubility and adsorption for Li₂ZrO₃, Li₄SiO₄ and Li₂TiO₃ are needed. Also the data for water vapor solubility and adsorption of Li₂ZrO₃, Li₄SiO₄ and Li₂TiO₃ are needed.
  For lack of enough data on irradiation effects for breeder ceramics, it is hereafter more needed to investigate irradiation behaviors for physical properties, thermal properties, mechanical properties, tritium transport, tritium retention and tritium release properties, helium transport and helium retention properties, fracture properties, and so on. In this case, Table 3-1 will be helpful for investigators. The more information for tritium release of Li₂O, Li₂TiO₃, Li₂ZrO₃ and Li₄SiO₄ is needed.
  However, owing to the limitation of our research and search activity, there may be still oversight of existing data. So the authors are very much grateful for being notified existing data as well as being assisted for collecting the data and/or supplied with them. Only with such collaboration, we can construct the complete database for breeding blanket materials.